ML19347D244

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Pump & Valve Test Program. Twenty-four Oversize Drawings Encl.Aperture Cards Are Available in PDR
ML19347D244
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 03/02/1981
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML19347D242 List:
References
PROC-810302-01, NUDOCS 8103110597
Download: ML19347D244 (63)


Text

O SECTION II PDIP AND VALVE TEST PR0rRM1 BRUNSWICK STEAM ELECTRIC PLLNT UNITS NOS. 1&2 IN-SERVICE INSPECTION PROGRAM

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Table of Contents Valve Test Program A. Program Summary B. Valve Test Program Table Formar C. Valve Program Tables D. Code Exceptions - Valve Test Program Pump Test Program A. . Program Summary B. Pump Test Program Table Format C. Pump Program Table D .' Code Exceptions 9

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VALVE TEST PROGRAM Brunswick Steam Electric Plant Unit Nos. I and 2 L

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VALVE TEST PROGRAM A. PROGRAM

SUMMARY

The Valve Test Program identifies test requirements for safety related valves; both-those valves tested in accordance with the requirements of Subsection IWV of the NsME Boiler and Pressure Vessel Code, 1977 Edition, and Addendum through Summer, 1978 Addendum and those valves for which

-the Code requirements have been found to be impractical.

Individual valve test requirements are presented in Section C by coded Valve Test Program Tables. The codes uscd for these tables are defined

'in Section-B and summarized in Figure 1. The Valve Test Program Tables of_Section'C are arranged'in' numerical sequence by In-service Inspection

' Drawing (ISD)onumber. Section D provides justifications for exceptions taken-to code test. requirements as provided for in 10CFR50.55a(g) (5) (iii).

Two types of justifications are provided. The first are general in

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nature and. pertain to requirements found to be impractical for all valves. .The second type is used to justify code exceptions f specific valves. . Code' exceptions are numbered and referenced by number en the Valve Test Program: Tables.

B. VALVE TEST PROGRAM TABLE FOPJfAT-Each Valve Test Program Table has been coded to_ provide the following information:

.1. -Valve Number. . Unique number assigned to each valve.

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2.. Class. -ASME Class.

- 3.:-- ' Coordinates. Location on the ISD where the valve is found.

4. Valve Category. .ValveLc" 1ar as defined in Subsection IWV-2200.
5. Passive. 'An "X".inithis.s indicates ' that a valve -is passive as defined in Subsection Ihi 'O. -All'other valves are active valves as described.~

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6. Size: Nominal diameter of valve.
7. Valve Type. The following is a list of the type of valve with the Code used in the Valve Test Program Tables to reflect the. valve type.

. AN - Angle Valve . PG - Plug

. BF - Butterfly . RD - Rupture Disk

. BL - Ball . RG - Regulating

. CK - Check . RL - Relief

. DA - Diaphragm . SC - Stop Check

. GA - Gate . SK - Spring Check

. GL - Globe . TW - Three Way

. ND - Needle

8. Actuater Type. The following is a list of the type of operator used to change the valve position with the Code used in' the Valve Test Program Tables to reflect the operator type.

. AO - Air-Operator

. MA - Manual Operator

. MO - Motor Operator

. SA - Self' Actuated

. 50 - Solenoid Operator

.- HO - Hydraulic Operator

. XP-- Exposive Operator

9. Normal Position. The following is a list.of valve posi-tions:during normal. operation and the-Ccde used in the
Valve.Tect-Program Tables to reflect that position.

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. OP -LOpen

- .- CL L- Closed

. .LO _ Locked Open.

. LC - Locked Closed

. LT'- Locked. Throttled

. TH - Throttled

. 14- -1 Valve position' determined by other system parameters as in the-case of check valves.

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! 10. Teet Requirement: This column indicates the Code test requirements which apply to the valve. The following is a list of the Codes used in the Valve Test Program Tables with the definition of what the Code reflects.

. S -

Valve shall be exercised to the position required to fulfill its function.

Category C check valves will be verified for forward flow, reverse flow, or both forward and reverse flow depending on the safety related

,2 function of the valve.

Valves with remote position indicators, which are used to verify valve exercising or timing will have their remote position indicators verified in accordance with Stetion XI, Section IWV-3300.

. F -

Valve with fail-safe actuator to be tested by observing the operation upon loss of actuator power.

. T -

Valve stroke time to be measured.

. R -

Safety and relief valves set points to be tested in accordance with ASME PTC 25.2 - 1976.

. D --

Explosive actuated valves or rupture disk tested in accord nce with IWV-3610 or I;;V-3620.

. L -

- Valve which is subject to leak-testing in accordance with Appendix J of 10CFR50 and technical specification requirements.

- 11. Code-Exception. If the valve is being tested in accordance with Section XI requirements, this column will be blank.

However, for valves which the Section XI requirements have

'been found to be' impractical','a reference number is

. entered in'the-column. This reference number is addressed

in Section 'D' with a complete explanation of the specific exception- and justification for that ' exception.

. 12... Alternate Testing. Tf the valve-is being cested in ac-

cordance with Section XI. requirements, - this column will be blank. However,.if the'Section XI-testing requirements 3

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have been found to be impractical for a valve, this column presents the testing that will be performed in lieu of the Section XI specified test. The coding used for this column is the same as for the Test Re-quirement Column, see Item 10.

13. Test Frequenev. The Codes used in this Column indicate the plant operational status that must be achieved be-fore a particular valve can be safely tested. For sim-plicity, only the three codes are used.

. Q -

Quarterly Valves in this category can be tested quarterly during normal operation.

. C -

Cold Shutdown Testing of valves in this category must be deferred until cold shutdown in order to avoid possiole adverse operational or safety situations.

Inservice valve testing is defined as: Valve testing will commence as soon as possible but no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching cold shut-down conditions.- Valve testing will proceed in a normal manner until all testing is complete or the plant is ready to return to power. A comple-tion of all valve testing is not'a prerequisite to return to power and any testing not completed at' the-end of one cold shutdown will be performed during subsequent cold shutdowns, starting from the last test. performed at the previous cold shut-down, to meet the code specified testing frequency.

Cold shutdown conditions are defined per the Plant

. Technical Specifications. 1

. R -- ' Refueling Testing of .alves in this category must be deferred until the plant is in'a. refueling interval in order to-avoid possible adverse operational or safety situations. -This designation is also used for explosive-actuated valve to indicate that valve is tested.in. compliance-with Code requirements.

14.; Remarks. Thf.s column is.provided-forfpertinent~informa-

. tion as appropriate:

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C. VALVE PROGPWI TABLES This section provides a tabulatian of all safety related valves, both those valves that are tested in accordance with the require-ments of Subsection IWV of the ASME Boiler and Pressure Vessel Code, 1977 Edition, and Addenda through Summer 1978 Addenda and those valves for which the Code requirements have been found to be impractical. A set of Valve Program lubles is provided for each ISD. These sets are arranged sequentially by ISD number.

S-

C. VALVE PROGRMI TABLES This section provides a tabulation of all safety related valves, ooth those valves that are tested in accordance with the require-ments of Subsection IWV of the ASME Boiler and Pressure Vessel Code, 1977 Edition, and Addenda through Summer 1978 Addenda and those valves for which the Code requirements have been found to be impractical. A set of Valve Program Tables is provided for each ISD. These sets are arranged sequentially by ISD numbet.

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. . - . - _ _ = . . .

4 j VALVE TYPE ACTUATOR TYPE TEST FREQUENCY

. 4

-8 Code Definition Code Definition Code Definition

, AN Angle Valve A0 Air Operator Q Quarterly

,!: BF Butterfly MA Manual Operator C Cold Shutdown

'f .BL' Ball M0 Motor Operator R Refueling

, CK~ Check SA Self Actuated DA Diaphragm SO Solenoid Operator

, GA Gate H0 Hydraulic Operator

'GL l Globe XP Explosive Operator ND Needle-4 PG Plug RD Rupture Disk RG Regulat ing

'RL- Relief SC, Stop Check

-SK Spring Check 7TW Three Way l NORMAL POSITION

, Code. Definition

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OP: Open -:

CL - Closed LO ' Locked Open LC --Locked Closed LT -Locked Throttled Th Throttled

" Valve position determined by other system parameters as in the case

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of check valves.

TEST EQUIPMENT Code Definition t S Valve -shall' be exercised to the _ position required to fulfill its function; ,

F. Valve 1with fail-safe' actuator to be-tested by observing the operation g, upon loss of" actuator power.

T: Valve stroke time to be measured.

R -Safety and relief valvesJset points.to be tested in accordance with.

ASME PT .25.,2 - 1976.

D. LExplosive actuated valves or rupture disk tested =in accordance with-

.IWV-3610 or IWV-3620.

lL , Valve which is subject to leak testing;in accordance with Appendix J of 10CFR50 and technical specification requirements.

' Figure l'-Valve: Test Program' Codes  ;

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SW-V19 3 C-6 X 20 BF F10 OP S Q T Q SW-V25 3 D-5 X 20 CK SA --

S Q FORWARD FLOW TEST.

SW-V20 3 C-5 X 20 BF 11 0 OP S Q T Q SW-V21 3 D-4 X 20 CK SA --

S Q FORWARD FLOW TEST. j SW-V14 3 C-4 X 20 RF F10 CL S Q T Q SW-V13 3 C-4 l X 20 BF 11 0 OP S Q T Q SW-V22 3 D-3 X 20 CK SA --

S Q FORWARD FLOW TEST.

SW-V16 3 C-3 X 20 BF M0 CL S Q T Q SW-V15 3 C-3 X 20 BP 11 0 OP S Q T Q SW-V23 3 D-2 X 20 CK SA --

S Q FORWARD FLOW TEST.

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SW-V201 -3 C-71 X 4 CK SA --

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SW-V203- 3 F-3 X '4 .CK St. ---

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SW-V204 3 F-3 X 4 CK SA --

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'SW-V202I 3 F-3 X 4 CK SA --

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SW-RV7 3 E-7 l X' O.75 RL SA --

R R SW-V279 3 E-7 X 1.5 CK' SA --

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SW-RV13 3 E-6 X 0.75 RL SA --

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SW-V213. 3: C-2' X .6 BF M0 CL S Q-T Q 2-SW--V275 ' 3 C-2 X 6. CK SA' --

.S~ Q FORWARD FLOW TEST.

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S Q FORWARD FLOW TEST.

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1-SW-V211 3 C X 6 BF 'M0 CL S Q T Q 1-SW-V273 3 C X 6 CK SA --

S Q FORWARD FLOW TEST.

2-SW-V211 3 C-5 X 6 BF MO CL 9 Q T Q 2-SW-V273 3 C-5 X 6' CK SA --

S i Q FORWARD FLOW TEST.

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ER NSWICK. STEAM ' ELECTRIC . PLWT, -U::ITS 1 3 - 2 Pace-2 of 2 D- VALVE TEST FP.CGr#4 iSyst<:n Elligli Pressure Coolant Inject ion .- tr.iwi t:. ::o. 9527-D-25023' "

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BRUNSWICK STCAM ELSCTRIC ?L7.NT,-UIIITS-l & 2 . p0.' 0 I of 2 VALVS TEST PROGRY4 Sys te: . RESIDUAL llEAT REMOVAL, D awing Mc'. 9527-D-25025 EC'**

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LRUNSWICK STEAM ELECTRIC 77.rT.'UM 73 l':r, 2 rage 2 or 2 VALVE TEST. PROGP1J"..

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- ERUNSWICK STEAM ELECTRIC PLNC, J 1:N7.TS 1- r . 2 pcge 1- og .2' VALVE : TEST l'ROOENI L Systdm - RESIDliAL llEAT REM (WAL Drawing 'to. 9527-D-25026 RCV. II

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LAUNSWICK' STEAM'3LECTRIC PLAF7, U;1IT3 1 & 2 pcge 2 of 2 VALVE TEST PROGPNI

' Drawing ' 9527-D-25026 Rev. I1 l: System RESIDUAL llEAT REMOVAL N.,.

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"s f DRUNSWICK STEN 4 ELisCTRIC ?.TI.'C, J U ' T*3 ^1 C. -2 ~ lpage 1 of. I 1

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' VAIRE TEST- PROGR701

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D. CODE EXCEPTIONS This section provides justification for the exceptions taken to Code tent requirements as provided for in 10 CFR 50.55a(g)(5)(iii).

Each Code exception is identified by a unique number and identifies the valve (s) for which the Code exception is being taken. The specific Code test requirement found to be impractical is defined and the basis for exclusion from Code requirements is presented.

Any. testing performed in lieu of Code requirements is specified.

Two types of justification are provided. The first are general in nature and pertain to Code requirements found to be impractical for all valves. The second type is used to justify Code exceptions for specific valves. Code exceptions are numbered and ref erer_ed by number on the Valve Test Program Talles for specific valves.

1. General Code Exceptions
a. Code Exception Number G-1

+ Components: All safety-related power-operated valves.

. Function: Power-operated valve timing requirements.

. Class: All.

. Test Requirement: Section XI, IWV-3413(b)

. "The stroke time of power-operated valves shall be measured to the nearest second or 10% of the maximum allowable stroke time, whichever is less, whenever such a valve is full-stroke tested."

Basis for Exception: For valves with stroke times less than 10 seconds--this would require measuring stroke

' times to be within a fraction of a second. Valve timing is performed using a stopwatch either by directly ob-serving valve movement or by observing remote position indicators. Neither method can be relied upon to yield results with accuracy of less than a second.

AlternateLTesting. The stroke time of all power-operated

~

valves'shall be-measured to the nearest second.

-b. Code ExceptionINumber'G-2 Components: All safety-related power-operated valves.

L

  • Function: Power-operated . valve timing requirements.

. Class: - All,.

L

Test Requirements: Section XI, IRV-3413(c)

"If an incresce in stroke time of 25% or more from the previous test for valves with stroke times greater than

10 seconds, er 50% or more for valves with stroke times
. less than or equal to 10 seconds, is observed, test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resumed."

(

3 asis for Exception: Operating experience has indicated that individual valve timing is influenced by many fac-tors such as changes in te=perature, humidity, fluctuations in power source, limit switch adjustment, etc. Because of these outside factors, timing data can exhibit scatter which exceeds the Code criteria but which is still less than the maximum full stroke time. Lacking in the Code requirements is any provision for verifying test results prior to placing the valve on an accelerated test frequency.

The present Code does not require any action for valves whose stroke time suddenly decreases a significant amount.

Any marked decrease outside the normal band of stroke times could indicate a major mechanical problem, such as the power operator being disconnected f rom the valve. Any significant decrease in stroke time should be investigated to determine if the valve and power actuator are capable of performing their function.

+ Alternate Testing: Maximum full stroke times shall be

~ establir>hed for each valve based upon required valve response time to assure adequate system response for safety-related functions. Valve test times will be

' acceptable if less than the maximum allowed. If test times exceed the maximum allowed, the valve will be immediately retested and corrective action taken as appropriate. Any significant decrease in valve test

. ttne will immediately be investigated and. appropriate corrective action-taken, f

I'

2. Sgecific Code Exceptions
a. Code Exception Number 1 Components: Cll-CV126, Cll-CV127, Cll-114 (typical of 137)
  • Category: B

+ Class: 2 Function: Control Rod Drive Scram Inlet and Exhaust Valves and Scram Discharge header check valves.

  • Test Requirement: Exercise valve for operability, observe proper operation of fail-safe mechanism, and measure stroke time quarterly.

Basis for Exception: These valves operate in coincidence

-to rapidly' insert control rods. Valves will be tested in accordance with plant Technical Specification 4.1.3.2.

This requires testing of all control rods prior to thermal power exceeding 40% of rated thermal power following core alterations or af ter a reactor shutdown exceeding 120 days.

Testing of 10% of the control rods, on a rotating basis, at least once per 120 days of operation.

  • Alternative Testing: Scram function timing will be sub-stituted for individual valve timing.
b. Code Exception Number 2

. Components: Cll-CVF010, Cll-CVF0ll

. Category: B

. Class: Non-Classed

. ' Function: - Scram Discharge Volume isolation valves.

. ' Test Requirements: Exercise valve for operability, observe . proper operation of fail-safe rechanism, and measure stroke. time quarterly.

. Basis for Exception: . Elf the' valve fails closed during cycling, water accumulates in the Scram Discharge Volume.

If more than 109 gallons accumulate, the reactor trips on

.high level in the Scram Discharge Volume- . Partial stroking is precluded by valve design.

- Alternative. Testing: Exercise valve for operability,

~o bserve proper operation ofLfail-safe mechanism,. and measure stroke time during cold shutdown.

w

c. Code Exception Number 3 Components: E41-V8, E41-V9
  • Category: B

+ Class: 2

  • Functien: HPCI Turbine Stop and Control Valves i

Test Requirement: Measure valve stroke time quarterly.

  • Basis for Exception: The purpose of these valves is to regulate steam to the HPCI Turbine. Operability of these valves is adequately demonstrated by turbine operation.

j Valve position is steam line pressure dependent and therefore will not repeatedly throttle to the same posi-tion. During t.urbine operation, these valves move in response to control signals.

  • Alternative Testing: Proper response of these valves will be verified during HPCI Turbine Test.
d. Code Exception Number 4

- Components: E41-F006

  • Category: B

+ Class: 1

+ Function: HPCI System Inlet to Feedwater System Iselation Valve.

Test Requirement: Exercise valve for operability and

= measure stroke time quarterly.

Basis for Exception:- Valve cannot be opened with normal operating Reactor Coolant System pressure differential

l. 'across the valve. Valve design precludes opening valve until cold shutdown when the pressure differential across the valve-is: low enough to allow valve operation.

- *: Alternative Testing: Exercise valve for operability and meaaure stroke time during cold shutdown.

A A

d a

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c. Code Exception Number 5 Components: E21-F006A, E21-F006B t

Category: C Class: 1 Function: Core Spray Injection Check Valve Test Requirement: Exercise valve for operability quarterly.

Basis for Exception: The only way to verify forward flow through the valve is to inject water from the Core Spray System through the valve into the reactor. Cycling the valve is impossible during normal operation when valve design precludes cycling against normal operating pressure.

Injection of the relatively cold water into the hot reactor during-cold shutdown would result in thermal shocking the vessel nozzles and could result in reactor vessel nozzle cracking.

Alternative Testing: Verify operability of the valve at refueling.

f. . Code Exception Number 6

. Components: E11-F050A, Ell-F050B Category: C Class: 1

. Function: ' Low Pressure Coolant Inj ection Check Valve.

. Inst Requirement: Exercise valve for operability quarterly.

. Basis'for Exception: The'only way to verify forward flow

-through. the check valve is to inject water from the Residual Heal Removal System through the valve into the Reactor Coolant System. .This cannot be accomplished during normal operation

.when the Reactor Coolant' System pressure is much greater than the Residual Heat Removal System operating pressure.-

. Alternative Testing: Verify forward flow operability of the

' valve by injecting water from the Residual Heat Removal System through the valve into the Reactor Coolant System at cold shutdown.

i s I I- $ -- , _

g. Code Ex.ception Number 7 Components: C41-F006, C41-F007 Category: C Class: 1 Function: Standby Liquid Control Injection Check Valve.

Test Requirement: Exercise valve for operability quarterly.

Basis for Exception: Forward flow verification can only be performed by firing on2 of the squib valves and injecting water using t'a pumps into the heactor Coolant System.

This would require realigning the system from the Standby Liquid Control Tank to the test tank which disables the system. Plant Technical Specification 3.1.5 requires the system to be operable and aligned to the control tank during normal operation and refueling for operations in-volving core alterations.

Alternative Testing: Forward flow verification will be performed in conjunction with the firing of one squib valve and injection into the Reactor Coolant System per Plant Technical Specifications 4.1.5 (c).

h. Code Exception Number 8 Components: B32-F031, F032 Category: B Class: 1 Function: Reactor Racirculation Loop Isolation Valves Test Requirement: Exercise valve for operability cnd measure stroke time quarterly.

Basis for Er.teption: Valves cannot be closed during power operations because isolating a loop will trip the reactor.

Valve design precludes partial stroking. Technical Specifica-tions require stroking at Cold Shutdown.

Alternative Testing Exercise valve for operability and measure stroke time during Cold Shutdown.

k PDT TEST PROGRAM i Brunswick Steam Electric Plant Unit Nos. I and 2 n -s .~- ' . . , . . - _ ~ . .- - _ - . - - _ - . - - _ _ . - -- - . . _ . - _ - _ _ - _ - - _ _ _ _ . _ _ _ - . - - _.

^

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(

PID!P TEST PROGRAM t

A. PROGRAM SU) DIARY The Pump Test Program identifies test requirements for all safety related pumps, both those pumps tested in accordance with the requirements of Subsection IWP of the ASME Boiler and Pressure Nessel Code, 1977 Edition, and Addendum through Summer, 1978 Addendum and those pumps for which the code requirements have been found to be impractical.

- Individual pump test requirements are presented in Section C by a coded

, Pump Test Program Table. The codes used for this table are defined in Section B. The Pump Test Program Table of Section C is arranged in numerical sequence.by In-service Inspection Drawing (ISD) number.

Section D provides justifications for exceptions taken to code test requirements as provided for in 10CFR50.55a(g) (5) (iii). Justifi- <

cations pertain to requirements found to be impractical for specific pumps. . Code exceptions are numbered and referenced by number on the Pump Test Program Table.

B. -PUMP TEST' PROGRAM TABLE' FORMAT

  • - The Pump Test Program Table has been coded to provide the following information:
1. System and Drawing-Number. System the pump is in and the ISD number.

Location on the ISD where the pump is found.

~

{z 2.  : Coor linates.

3. - Pump ~ Number. Unique number assigned to each pump.
4. . Speed n*. These parameters are addressed with one of the follow-ing entries, which indicate test interval or applicability:

. TNR - nct required

. NA - n'ot available

. M: '- monthly test.

. .Q ~ , quarterly test

. C cold shutdown test-1 1

e 1

5. Inlet Pressure P4 Same as Number 4.
6. Differential Pressure up. Same as Number 4.
7. Flow Rate Q. Same as Number 4.

8 .' Code Exception. If the pump is being tested in accordance with Section XI requirements, this column will be blank. Powever, for ptmips which the Section XI requirements have been found to be ,

impractical, a reference number is entered in the column. This reference number is addressed in Section D with a complete explanation of the specific exception and justification for that~ exception.

, ~ C. PintP PROGRAM TABLE This section provides a tabulation of all safety related pumps; both those pumps that are tested in accordance with the requirements of Subsection IWP Of the ASME Boiler and Pressure Vessel Code, 1977

! Edition,.and Addendum'through Summer, 1978, Addendam'and those pumps

-for which.the code requirements have been found to be impractical.

The table is' arranged sequentially by ISD' number.

4 2-f, s 5 m

n

'7 M

s.

BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 & 2

  • PUMP TEST PROGRAM Page 1 of 2
  • TEST PARAMETER MEASUPID

, SYSTEM

& y INLET DIFFERENTIAL FLOW VIBRATION DRAWING. BEARING LUDRICANT g.Q . PUMP SPEED PPSSSURE PPESSURE RATE AMPLITUDE TEMPERATURE LEVEL OR CODE NU CER y5 NO. n* Pi 6p Q V Tb PRESSURE EXCEPTION SW (NUCLEAR) E-7 A HR Q Q Q NR Q ,

NR 1, 2, 3,7 E-6 B NR Q Q Q Q NR NR 1, 2, 3,7

(CONVEN- E-4 A NR Q Q Q UR Q NR 1, 2, 3,7 E-3 B NR .Q Q Q Q NR MR 1, 2, 3,7 9527-D-20041 E-2 C UR Q Q Q NR Q NR 1, 2, 3,7

!6 gg LUBRICATING F-3 A NR Q Q Q Q NR NR 1, 2, 3,7

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95 -20041 E E " ' ' '

% I!PCI ' C-1 Main .Q Q I

Q Q Q NR NR 1, 2, 3,7 9527-D-25023 CORE SPRAY D-6 A NR Q Q Q NR

, Q NR 1, 2, 3,7 9527-D-25024 D-6, l B NR Q Q Q NR Q NR 1, 2, 3,7 MIR E-5 A NR Q Q Q NR Q NR 1, 2, 3,7 9527-D-2$025 E-7 ', C UR Q Q Q UR Q NR 1, 2, 3,7

( RffR F-2 B NR Q Q Q Q NR NR 1, 2 , 3 ,7 9527-D-25026 P-1 D NR Q Q Q NR g Q NR 1, 2, 3.7 1

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'SYt'CllRONOUS OR INDUCTION MOTORS DO NOT REQUIRE SPEED Cl!ECF2' (IWP-4400) .

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BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 & 2 -

PUMP TEST PROGRAM Page 2 of 2

SYSTEM TEST PAPA 14ETER MEASURED

& y INLET DIFFERENTIAL DRAWING FLOW VIBRATION BEARING Q. PUMP. SPEED PRESSUPS LUB RICA'IT PRESSURE RATE AMPLITUDE NUMBER o$ NO. .n* Pi Ap Q V TEMPCPATURE T3 LEVEL OR CODE PRESSURE EXCEPTION RI'R SW D-5 A NR Q Q BOOSTER Q Q NR NR 1, 2, 3,7 n-3 3 NR Q Q Q Q NR NR 1, 2, 3,7 9527-D-25037 B-4 -C NR Q Q Q Q NR NR 1, 2, 3,7 B-3 D NR Q Q Q Q NR NR 1, 2, 3,7 SIC D-4 A NR Q- Q Q NR NR NR 1,2,3,4,5,67 ui 9527-D-25047 E-4 -B NR Q Q Q NR NR NR 1,2,3,4,5,67 l

! *SYNCl!RONOUS OR INDUCTION MOTORS DO NOT REQUIP 2 SPEED Cf!ECN (IWP-4400).

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D. CODE EXCEPTIONS This section provides justification for the exceptions taken to code test requirements as provided for in 10CFR50.55a(g) (5) (iii). Each code exception is identified by a unique number and identifies the pump (s) for which the code exception is being taken. The specific code test requirement found to be impractical is deffned and the basis for

-exclusion from code requirements is presented. Any testing performed i in lieu of code requirements is specified. Code exceptions are numbered and referenced by number on the Pump Test Program Table for specific pumps.

1. Code Exceptions
a. Code Exception Number 1

. Components: Nuclear Service Water Pumps A, B Conventional Service Water Pumps A, B, C Service Water Lubrication Water Pumps A, B Core-Spray Pumps A, B Residual Heat Removal Pumps A, B, C, D Residual Heat Removal Service Water Booster Pumps A, B High Pressure Coolant Injection Pump Standby Liquid Control Pump A, B

. Function: Emergency Core Cooling Safety Related Equipment Cooling Safe Reactor Shutdown

. ' Class: 2 and 3 c.- Test Requirement: Monthly In-service Test

. Basis for Exception: Monthly Section XI operability testing has been a plant requirement for these pumps since March 1,~1978. An analysis of the results of these tests and comparable data from other operating plants has shown no significant changes in performance.

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Based on-this analysis,'the continuation of Section XI monthly testing would not significantly increase plant safety.

Monthly pump testing requires a total of at least 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> ~per year _of pump operation; at least 700 man-hours per year for data acquisition; at least 60 man-heurs;per

-year for data reduction,' analysis, and record keeping.

This amounts to a total ofi760 man-hours per year. At a

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conservative total' cost of.$20 per man-hour, this amounts to $15,200 periyear. : Based upon the' average exposure

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rates in the pump access areas, the total man-rems exposure per year for pump testing is approximately 1.0 man-rems. At the present conservatively estimated cost of S10,000 per man-rem to plant personnel, this exposure costs an additional $10,000 per year. Total cost to our customers is approximately $25,200 per year, for no significant increase in safety.

. Alternate Testing: Pumps will be tested in compliance witn ASME-Section XI once per quarter. This is in agreement with present changes that are being imple-mented with Subsecticn IWP of the code.

The revision to change the pump testing to a three-month interval in IWP-3400, has been approved and incorporated in Section XI by the Winter, 1979 Addendum.

b. Code Exception Number 2

. . Components: Nuclear Service Water Pumps A, B Conventional Service Water Pumps A, B, C

Service Water Lubrication Water Pumps A, B Core Spray Pumps A, B Residual Heat Removal Pumps A, B C, D Residual Heat Removal Service Water Booster Pumps .A, B Standby Liquid Control Pumps A, B High Pressure Coolant Injection Pump

. Function: Emergency Core Cooling Safety Related Equipment. Cooling Safe Reactor Shutdown

. Class: 2 and 3

. 1 Test Requirement: ' Measure pump bearing temperature yearly.

. Basis for Exception: .The referenced _ edition of the code requires bearing temperature to be recorded annually.

It has been' demonstrated by experience that bearing temperature rise occurs only minutes prior to bearing failure.

Therefore, the' detection of possible bearing failure by a yearly temperature measurement is extremely unlikely. -It requires lat'least an hour of pump operation to achieve

- stable bearing temperatures. The-small probability of

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detection bearing failure by temperature measurement does not justify the additional pump operating time required to obtain the measurements.

e Alternate Te. Sting: NONE. This is in agreement with present changes that are being implemented in Subsec-tion IWP of the Code. The revision to delete yearly bearing temperature measurement. Deletion of bearing temperature has been approved and will be included in future Addenda. See minutes of the November 28, 1979 meeting of the Operating and Maintenance Working Group -

Testing of Pumps and Valves in San Jose, California, dated January 9, 1980.

c. Code Exception Number 3 e Components: Nuclear Service Water Pumps A, 3 Conventional Service Water Pumps A, B, C Service Water T_brication Water Pumps A, B Core Spray Pumps A, B Residual Heat Removal Pumps A, B, C, D Residual Heat Removal Service Water Booster Pumps A, B Standby Liquid Control Pumps A, B High Pressure Coolant Injection Pump e Function: Emergency Core Cooling Safety Related Equipment Cooling Emergency Boron Injection e Class: 2 and 3 e . ~ Test Requirements: Observation of proper lubrication level or pressure.

e Basis for Exception: The observation of lubrication level or pressure is a maintenance function not an operability

~

test function. Pu' m p lubrication requirements are deter-mined by the pump manufacturer and plant operation.

  • Alternate Testing: Pump lubrication requirements are part of the plant maintenance procedures rather than Section XI operabf.lity test. requirements. This'is in agreement _with present changes that are being implemented in Subsection IWP of the Code. - The:- revision to. eliminate observation of

~

lubrication level or pressure from the Code. has been approved and will:be included in future Addenda. See minutes of the

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November 28, 1979 meeting of the Operating and >bintenance Working Group - Testing of Pumps and Valves, in San Jose, California, dated January 9, 1980.

d. Code Exception Number 4

. Components: Standby Liquid Control Pumps A, B

. Function: Provide a method of shutting down the Reactor without use of control rods.

. Class: 2

. Test Kequirement: Run pumps for five minutes under stable conditions (per IWP-3500).

. Basis for Exception: Pump is tested by pumping deminera-lized water into a test tank. The tank capacity does not r

allow operation of the pump for five minutes. Pump design

.does not require a specified operating time to reach stable operating-conditions.

Alternat'e Testint* Pump test time will be determined by

~

test tank volume.

e. Code Exception Number 5

. ~ Components:

Standby Liquid Control Pumps A, B Function: Provide a method of . shutting down the Reactor

.without use of control rods.

. Class: >2

, . . Test Requirement: Measure pump vibration.

,. Basis for Exception: The' Standby Liquid Control pumps are reciprocating ' positive displacement pumns and there-fore, any vibration measurements made on the pump would only indicate amplitude _ readings. corresponding.to piston movements. Any vibration readings on this type of pump are useless in determining pump-degradation.

tAlternate Testing: NONEI-

.i f.: . Code Exception Numberz 6'- m.

. - Components: Standby. Liquid Control Pumps A, B-

.: Function: ; Provide a method of shutting down the Reactor-

without useJof! control rods.

. Class: 2 ,

-g. L9

1

. Test Requirement; Measure flow rate

. Basis for Exception: Instrumentation is not installed to measure flow rate. Present test method measures level chenge in a test tank over a period of time to determine flow rate.

. -Alternate Testing: The present method will be used to determine flow rate.

c. Code Exception Number 7

. Components: Nuclear Service Water Pumps A, B Conventional Service Water Pumps A, B, C Service Water Lubrication Water Pumps A, B Core Spray Pumps A, B Residual Heat Removal Pumps A, B, C, D Residual Heat Removal Service Water Booster Pumps A, B Standby Liquid Control Pumps A, B High Pressure Coolant Injection Pump

. Function: Emergency Core Cooling Safety Related Equipment Cooling

' Safe Reactor Shutdown

- .- I Class: ~ 2 and 3-I N . Test Requirement: Instruments shall meet the accuracy

.' requirements.of Table IWP-4110-1.

. . Basis for Exception: . Installed station. instruments for measuring. pump _ pressures and flows meet sufficient ~ accuracy requirements to enable the pump;to perform its safety-related fuaction. - The instruments are calibrated;per technical-specification. frequencies.

- .- zAlterna'te Testing: Installed station. instruments will be

~

- used for measuring pump parameters wherever possible.

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8 Brunswick Steam Electric, Plant Unit Nos. 1 and 2 In-Service Inspection Program Reference Information Following is a list of drawings that are a part of the BSEP ISI Program:

Reference No. Drawing No.

1 ISD-9527-D-20041 1A ISD-9527-D-2274 1B ISD-9527-D-25037 2 ISD-9527-D-2560 2A ISD-9527-D-25015 2C ISD-9527-F-40073 3 ISD-9327-D-25016 3A ISD-9527-D-25017 4 ISD-9527-D-25018 4A ISD-9527-D-25048

-5 ISD-9527-D-25021 SA ISD-9527-D-25022 6 ISD-9527-D-25023 7 ISD-9527-D-25024 8 ISD-9527-D-25025 8A . ISD-9527-D-25026 9 ISD-9527-D-25027-10 ISD-9527-D-25029

- 11 ISD-9527-D-25038 12 ISD-9527-D-25042 13 ISD-9527-D-25045-14- ISD-9527-D-25047

- 15 ISD-9527-D-25049 16 ISD-9527-D-26098 One set of these drawings has been marked-up for NRC in order to highlight Item Numbers and piping classes which will simplify referencing. Color coding is as follows:

Pink: ASME Class 1-Yellow: 'ASME Class 2 Green: ASME Class 3 e

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